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Journal Articles

Microstructure and texture evolution and ring-tensile properties of recrystallized FeCrAl ODS cladding tubes

Aghamiri, S. M. S.*; Sowa, Takashi*; Ukai, Shigeharu*; Ono, Naoko*; Sakamoto, Kan*; Yamashita, Shinichiro

Materials Science & Engineering A, 771, p.138636_1 - 138636_12, 2020/01

 Times Cited Count:33 Percentile:90.54(Nanoscience & Nanotechnology)

Oxide dispersion strengthened (ODS) FeCrAl ferritic steels are being developed as potential accident tolerance fuel cladding materials for the light water reactors (LWRs) due to significant improvement in steam oxidation by alumina forming scale and good mechanical properties up to high temperatures. In this study, the microstructural characteristics and tensile properties of the two FeCrAl ODS cladding tubes with different extrusion temperatures of 1100$$^{circ}$$C and 1150$$^{circ}$$C were investigated during processing conditions. While the hot extruded sample showed micron sized elongated grains with strong $$alpha$$-fiber in $$<$$110$$>$$ texture, cold pilger rolling process change the microstructure to submicron/micron size grain structure along with texture evolution to both $$alpha$$-fiber ($$<$$110$$>$$ texture) and $$gamma$$-fiber ({111} texture) via crystalline rotations. Subsequently, final annealing resulted in evolution of microstructure to large grain recrystallized structure starting at recrystallization temperature of $$sim$$810-850$$^{circ}$$C. Two distinct texture development happened in recrystallized cladding tubes, i.e., only large elongated grains of (110) $$<$$211$$>$$ texture following extrusion temperature of 1100$$^{circ}$$C; and two texture components of (110) $$<$$211$$>$$ and {111} $$<$$112$$>$$ following higher extrusion temperature of 1150$$^{circ}$$C. The different texture development and retarding of recrystallization progress in 1100$$^{circ}$$C-extruded cladding tubes were attributed to higher distribution of oxide particles.

Journal Articles

Purification of uranium products in crystallization system for nuclear fuel reprocessing

Takeuchi, Masayuki; Yano, Kimihiko; Shibata, Atsuhiro; Sambommatsu, Yuji*; Nakamura, Kazuhito*; Chikazawa, Takahiro*; Hirasawa, Izumi*

Journal of Nuclear Science and Technology, 53(4), p.521 - 528, 2016/04

 Times Cited Count:2 Percentile:19.57(Nuclear Science & Technology)

Journal Articles

Microstructural evolution during creep of Ni-base solid solution alloys and in-situ observation at high temperature

; *; Kikuchi, Kenji; ; Miura, Takayuki*

Proc. of 4th Int. Conf. on Recrystallization and Related Phenomena (REX'99), p.283 - 288, 1999/00

no abstracts in English

Journal Articles

Creep damage in welded joints of a Ni-base heat-resistant alloy hastelloy XR

*; ; *; Tsuji, Hirokazu; *; Shindo, Masami

Mater. Sci. Eng., A, 234-236, p.1087 - 1090, 1997/00

no abstracts in English

Journal Articles

Creep properties of 20% cold-worked Hastelloy XR

Kurata, Yuji; Nakajima, Hajime

Journal of Nuclear Materials, 228, p.176 - 183, 1996/00

 Times Cited Count:12 Percentile:70.53(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Effect of cold work on creep properties of Hastelloy XR

Kurata, Yuji; Nakajima, Hajime

JAERI-Research 94-004, 30 Pages, 1994/08

JAERI-Research-94-004.pdf:2.99MB

no abstracts in English

JAEA Reports

Creep properties of 20% cold worked Hastelloy XR

Kurata, Yuji; Nakajima, Hajime

JAERI-M 94-022, 28 Pages, 1994/02

JAERI-M-94-022.pdf:0.9MB

no abstracts in English

Journal Articles

Effect of cold work on creep properties of Ni-22Cr-18Fe-9Mo alloy

Kurata, Yuji; Hamada, Shozo; Nakajima, Hajime

Proc. of 10th Int. Conf. on Strength of Materials; ICSMA 10, 0, p.677 - 680, 1994/00

no abstracts in English

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